PRESENT ANALYSES OF RADIATION EXPOSURE SUCH AS PREPARED FOR WASH-1400, GESMO AND IN REACTOR LICENSING ACTIONS HAVE NOT BEEN UNIFORM
IN DOSE ESTIMATION METHODOLOGY. THE VARIOUS APPROACHES USED FOR THE ABOVE STUDIES AND ACTIONS REFLECT VARIOUS INTERPRETATIONS OF
THE STATE-OF-THE-ART IN DOSE ESTIMATION MEHODOLOGY, THE NEEDS OF PARTICULAR STUDIES AND AVAILABILITY OF DOCUMENTED MODELS. NRC
DOES NOT HAVE A BROADLY APPLICABLE, DOCUMENTED, CRITICALLY REVIEWED, STATE-OF-THE-ART DOSE ESTIMATION METHODOLOGY AVAILABLE TO
VARIOUS OFFICES FOR THEIR ASSESSMENT NEEDS. THE CLOSEST IS REGULATORY GUIDE 1.109, REVISION 1, 1977, WHICH REPRESENTS A CURRENTLY
APPROPRIATE APPLICATION OF A REASONABLE UP-TO-DATE DOSE ASSESSMENT METHODOLOGY AS APPLICABLE TO NUCLEAR POWER PLANT EFFLUENTS.
THE OFFICE OF NUCLEAR REGULATORY RESEARCH RECOGNIZED THE NEEDS IN THIS AREA, AND HAS BEEN FUNDING RESEARCH AT THE HEALTH AND
SAFETY RESEARCH DIVISION OF THE OAK RIDGE NATIONAL LABORATORY CORNL). THE RESEARCH DESCRIBED IN RIL 047 PARTIALLY FULFILLS THE
NEED OF A BROADLY APPLICABLE, DOCUMENTED AND CLOSER TO THE STATE-OF-THE-ART MODEL FOR CALCULATION OF DOSES TO VARIOUS ORGANS OF A
BODY FROM INTERNALLY DEPOSITED RADIONUCLIDES. HOWEVER, ITS APPLICATION TO REGULATORY PROCESSES HAS TO WAIT UNTIL SOME ADDITIONAL
SUPPORTING RESEARCH IS COMPLETED (SEE COMMENTS/REMARKS) MOST OF WHICH ARE ON-GOING AT ORNL FUNDED BY RES AND SOME BENCH-MARK
COMPARISONS ARE MADE.

ICRP HAS AN ONGOING CONTRACT W/HEALTH & SAFETY RESEARCH DIV. OF ORNL TO DEVELOP REVISED NUCLEAR DATA, S-FACTORS, METABOLIC PARA-
METERS, DOSIMETRIC MODELS, ETC. FOR USE IN ICRP'S FORTHCOMING PUBLICATION #30. IT IS NOT KNOWN THAT ORNL INTERNAL DOSIMETRY MODEL
FOR ICRP IS SOMEWHAT DIFFERENT FROM THAT FOR NRC (INREM-II) ALTHOUGH BOTH MODELS ARE BASED ON ICRP'S TASK GROUP LUNG MODEL (1966,
1972)& EVE'S GI-TRACT MODEL (1966). ORNL MODEL FOR ICRP IS MORE COMPLETE IN THAT IT HAS THE BODY FLUIDS (BLOOD) REPRESENTED IN
MODEL AS ADDITIONAL COMPARTMENT WHICH IS LACKING IN INREM-II. INCLUSION OF A BLOOD COMPARTMENT IS APPROPRIATE CONCEPTUALLY AS WELL
AS FROM VIEW POINT OF REALISTIC MODELING, IT IS LIKELY TO REDUCE THE ORGAN DOSE CONVERSION FACTORS PARTICULARLY FOR THE SHORTER
LIVED RADIONUCLIDES DUE TO DECAY DURING PARTIAL HOLD-UP IN BLOOD. BENCHMARKING INREM-II RESULTS W/ICRP'S WILL BE PRUDENT BEFORE
OUR USING THEM. BEST VALUES OF METABOLIC PARAMETERS REQUIRED AS INPUTS TO RUN INREM-II ARE NOT YET AVAILABLE. NOMINAL VALUES OF
PARAMETERS USED BY AUTHORS OF 2 VOLUMES (VOL. 2 IN PREPARATION OF DOSE CONVERSION FACTOR TABULATIONS ARE FOR PURPOSES OF ILLUSTRA-
TING USE OF INREM-II, & AUTHORS DO CAUTION AGAINST UNCRITICAL USE OF THESE TABLES IN RADIOLOGICAL APPLICATIONS BECAUSE THEY CON-13
SIDER THESE RESULTS AS PRELIMINARY. RES SHOULD BE REQUESTED TO INCLUDE TASK OF GENERATING & PERIODICALLY UPDATING DATA LIBRARY OF
BEST VALUES OF METABOLIC PARAMETERS FOR USE IN INREM-II IN THEIR CONTINUING RESEARCH PROGRAMS WITH ORNL. A SET OF VALUES OF META-
BOLIC PARAMETERS IS BEING USED IN ICRP WORK AT ORNL. ICRP VALUES ARE NOT YET AVAILABLE TO USE, BUT WHEN AVAIL, IT WILL BE PRUDENT
TO COMPARE VALUES H/PRELIMINARY VALUES USED BY ORNL FOR NRC, & MAKE APPROPRIATE REVISION IF NECESSARY. NUCLEAR DATA DEVELOPED &
UTILIZED BY ORNL FOR NRC NOT NECESSARILY SAME AS BEING DEVELOPED FOR ICRP. THOUGH SUBSTANTIAL DIFFERENCES NOT ANTICIPATED IN AREA,
IT WILL BE PRUDENT TO COMPARE DATA ALSO.

BIL TITLE: A TECTONIC OVERVIEW OF THE CENTRAL MIDCONTINENT SPONSORING OFFICE(S): SD, NRR

"A TECTONIC OVERVIEW OF THE CENTRAL MIDCONTINENT", NUREG-0382, IS THE MOST UP-TO-DATE SYNTHESIS OF GEOLOGIC KNOWLEDGE OF THE EARTHS CRUST IN THE STUDY AREA. IT CONTAINS THE MOST COMPLETE BIBLIOGRAPHY OF THE GEODYNAMICS OF THE AREA AND WILL AID IN NUCLEAR POWER PLANT LICENSING. IT IS RECOMMENDED THAT THE INFORMATION AND HYPOTHESES BE USED AS INPUT TO THE DEVELOPMENT OF A TECTONIC PROVINCE OR SEISMIC ZONING MAP OF THE EASTERN U.S. AND TO PROVIDE A BASIS AND GUIDE FOR ONGOING STUDIES IN THE AREA.

FILTRATE OF BLOOD SERUM AND 0. IM HCL. THE MEASUREMENT OF THE SOLUBILITY OF VARIOUS FORMS OF YELLOWCAKE IN VITRO UTILIZED THO SOLVENT SYSTEMS A SIMULANT OF AN ULTRATHE RESULTS OF THIS STUDY WILL BE USED TO DETERMINE WHETHER YELLOWCAKE SHOULD BE CONSIDERED A SOLUBLE COMPOUND WITH RESPECT TO 10 CFR 20. THE DATA OBTAINED USING THE SERUM SIMULANT SHOW THAT 25 TO 64 PERCENT OF ALL SAMPLES THE PURPOSE OF EXPOSURE CONTROL. TESTED DISSOLVED WITH HALF-TIMES LESS THAN 16 HOURS. IDEALLY, SOLUBILITY CLASSIFICATIONS SHOULD BE BASED ON THE DISSOLUTION HALFTIMES OF THE PARTICULAR PRODUCT UNDER CONSIDERATION. THE DATA INDICATE THAT YELLOWCAKE SHOULD BE TREATED AS A CLASS D COMPOUND FOR

OFFICE: SD IMPACT STATEMENT

THIS TOPIC IS PRESENTLY CONTEMPLATED. THE RESULTS OF THIS RESEARCH WILL BE USED IN FINALIZING REGULATORY GUIDE 8.22, "BIOASSAY AT URANIUM MILLS." NO FURTHER RESEARCH ON

SINCE 1957, THE NUCLEAR SAFETY GUIDE HAS PROVIDED USERS OF FISSIONABLE MATERIAL WITH SIMPLE METHODS TO ASSURE SYSTEM SUBCRITICAL-
ITY. RESEARCH INFORMATION LETTER 950 TRANSMITS NUREG/CR-0095, "NUCLEAR SAFETY GUIDE, TID-7016, REVISION 2." THIS REVISION
UTILIZES IMPROVED CRITICALITY DATA AND COMPUTATIONAL TECHNIQUES NOT AVAILABLE IN THE PREVIOUS GUIDE ISSUED IN 1961. REVISION 2
SHOULD BE REGARDED AS A SUPPLEMENT TO PREVIOUS GUIDES SINCE IT DOES NOT HAVE INTENTIONAL CONSERVATISMS INCLUDED AS IN PREVIOUS
GUIDES. IN USING REVISION 2 OF THE GUIDE, THE USER MUST IMPOSE APPROPRIATE SAFETY FACTORS FOR HIS APPLICATION AND THE NRC STAFF
MUST DETERMINE THAT THE SAFETY MARGINS PROPOSED BY THE USER OF REVISION 2 ARE ADEQUATE.

THE REVISED NUCLEAR SAFETY GUIDE IS QUOTED TO THE LICENSEES WHENEVER THEIR AMENDMENT OR RENEWAL OF APPLICATIONS REFER TO THE 1961
VERSION OF THE GUIDE AND FAIL TO RECOGNIZE NEW DEVELOPMENTS IN NEUTRON INTERACTION-ACTION, CERTAIN OF WHICH ARE SUMMARIZED IN THE
UPDATED GUIDE. THESE NEW DEVELOPMENTS, SOME OF WHICH HAVE RESULTED FROM NRC-SPONSORED RESEARCH, HAVE RENDERED QUESTIONABLE CERTAIN
PAST PROCEDURES IN THE ANALYSES OF NEUTRON INTERACTION.